2420 核融合炉内冷却材侵入時の二相流挙動に関する数値予測

概要

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An integrated ingress-of-coolant event (ICE) test facility was constructed to investigate two-phase flow behavior in the International Thermonuclear Experimental Reactor (ITER) during an ICE event. To predict numerically the experimental results with the integrated ICE test facility, an analytical study was carried out with the TRAC code which is a thermofluid safety analysis code for light-water reactors. The analytical results could simulate well pressure rise and two-phase flow characteristics in a vacuum vessel of the integrated ICE test facility. It was found from this study that the pressure suppression system in ITER during the ICE event is very effective and its performance and two-phase flow behavior can be predicted sufficiently with the TRAC code.
一般社団法人日本機械学会の論文
2000-07-31